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    • 101. 发明公开
    • 방사능 자동 측정 및 실시간 모니터링 방법
    • 用于自动检测和记录辐射的方法
    • KR1020140115779A
    • 2014-10-01
    • KR1020130030865
    • 2013-03-22
    • 주식회사 오리온이엔씨
    • 이운장
    • G01T1/167G01N1/10
    • G01T1/167G01T7/02G01T7/04G01T7/12
    • The present invention relates to a method for automatically measuring radioactivity and monitoring radioactivity. The present invention comprises a water supply step of collecting water from a water source by a water supply unit and providing the water to a measurement chamber; a measuring step of measuring radioactivity concentration of the water by the measurement chamber and transmitting the measured concentration to a control unit; a step of classifying and analyzing the transmitted data by the control unit and determining whether the water is contaminated or not; a washing step of operating a washing water supply unit when the water is contaminated and washing the measurement chamber; and a storage step of storing the contaminated water discharged from the measurement chamber by a contaminated water storage unit.
    • 本发明涉及一种自动测量放射性和监测放射性的方法。 本发明包括供水步骤,通过供水单元从水源收集水并将水提供到测量室; 测量步骤,通过测量室测量水的放射性浓度并将测量浓度传输到控制单元; 由控制单元对发送的数据进行分类和分析并确定水是否被污染的步骤; 洗涤步骤,当水被污染并洗涤测量室时操作洗涤水供应单元; 以及存储步骤,通过污染储水单元储存从测量室排出的污染水。
    • 102. 发明公开
    • 방사능 자동 측정 및 실시간 모니터링 시스템
    • 用于自动检测和单色辐射的系统
    • KR1020140115778A
    • 2014-10-01
    • KR1020130030864
    • 2013-03-22
    • 주식회사 오리온이엔씨
    • 이운장
    • G01T1/167G01N1/10
    • G01T1/167G01T1/20G01T1/24G01T7/02G01T7/12
    • The present invention relates to a system for automatically measuring and monitoring radioactivity. The system comprises a water supply unit which collects water from a water source by a pump; a measuring unit which stores the water supplied from the water supply unit and measures radioactivity concentration; a control unit, which collects water by transmitting a signal to the water supply unit and the measuring unit and operating the pump of the water supply unit, and which determines whether radioactivity exceeds the standard by receiving and analyzing the radioactivity data measured by the measuring unit and supplies water to the measuring unit from the water supply unit or blocks water depending on the determination; and a transceiving unit, which transceives the data of the control unit to/from a server in a wired or wireless method.
    • 本发明涉及一种用于自动测量和监测放射性的系统。 该系统包括通过泵从水源收集水的供水单元; 测量单元,其存储从供水单元供应的水并测量放射性浓度; 控制单元,其通过向供水单元和测量单元发送信号并且操作供水单元的泵来收集水,并且通过接收和分析由测量单元测量的放射性数据来确定放射性是否超过标准 并且从供水单元向测量单元供水,或者根据确定来阻止水; 以及收发单元,其以有线或无线方式将控制单元的数据收发到/从服务器发送。
    • 106. 发明授权
    • HPGe 측정기를 이용한 주괴 내의 방사능물질 측정방법
    • 测量放射性物质的方法,使用HPGE GAMMA SCINTILLATOR
    • KR101212062B1
    • 2012-12-13
    • KR1020120046978
    • 2012-05-03
    • 한전원자력연료 주식회사
    • 조석주이영배설증군김용재류재봉
    • G01T7/00G21C17/00
    • G01T1/167
    • PURPOSE: A method using an HPGe(High-Purity Ge) measuring device for measuring radioactive substances in an ingot is provided to rapidly determine the existence of radioactive substances in uranium by measuring gamma rays with the HPGe measuring device, thereby rapidly determining self-disposal of the melt-decontaminated ingot of metal wastes. CONSTITUTION: A method using an HPGe measuring device for measuring radioactive substances in an ingot is as follows. Metal wastes generated when treating or manufacturing a nuclear fuel are sorted depending on sources and melt-decontamination is performed so that an ingot of 1 to 10cm thickness is manufactured. Gamma rays emitted from the ingot with respect to a U-235 among uranium isotopes are measured by using the HPGe measuring device(S10). A self-absorption correction depending on medium density using a MCNP(Monte Carlo N-Particle) computer code and a measuring device correction by a certified reference material are performed and the radioactivity and mass of the U-235 are quantified and a whole uranium weight is calculated depending on the enrichment of the U-235 determined by the source of the metal wastes(S30) so that a radioactivity value of the whole uranium of the ingot is obtained(S40). [Reference numerals] (AA) Formula for calculating whole specific radioactivity of uranium; (S10) Measuring U-235(185.72keV); (S20) Quantizing amount of the U-235(Specific radioactivity = 80,000 Bq/g); (S30) Calculating whole uranium amount; (S40) Calculating whole radioactivity of the uranium
    • 目的:使用用于测量锭中放射性物质的HPGe(高纯度Ge)测量装置的方法,通过用HPGe测量装置测量γ射线来快速确定铀中的放射性物质的存在,从而快速确定自身处置 的金属废物熔融去污锭。 构成:使用HPGe测量装置测量锭中放射性物质的方法如下。 在处理或制造核燃料时产生的金属废物根据来源进行分选,进行熔融去污,从而制造厚度为1〜10cm的锭料。 通过使用HPGe测量装置测量从铀相对于铀同位素中的U-235发射的γ射线(S10)。 进行使用MCNP(蒙特卡洛N-粒子)计算机代码和通过认证参考材料的测量装置校正的取决于介质密度的自吸收校正,并且对U-235的放射性和质量进行量化和整个铀重量 根据由金属废物源确定的U-235的富集计算(S30),从而获得锭的整个铀的放射性值(S40)。 (附图标记)(AA)用于计算铀的整体比放射性的公式; (S10)测量U-235(185.72keV); (S20)U-235的量化量(比放射性= 80,000Bq / g) (S30)计算铀总量; (S40)计算铀的整体放射性
    • 107. 发明公开
    • 라돈 측정 표준 장비
    • 提供RADON气体标准化测量的设备
    • KR1020120094773A
    • 2012-08-27
    • KR1020110014236
    • 2011-02-17
    • 한국표준과학연구원
    • 김병철이경범박태순오필제이민기이종만이상한
    • G01T1/167G01T7/00G01N15/06
    • G01T1/167G01N15/06G01T7/04Y10S250/02
    • PURPOSE: A standard device for measuring radon is provided to supply a radon gas supplied from a radon source to a radon chamber after passing through a buffer chamber, thereby enhancing the purity of a radon being returned to a chamber for a distribution and absorbed in the radon chamber. CONSTITUTION: A standard device for measuring radon comprises a radon source(24), a radon chamber(14), and a vacuum pump(12). The radon chamber is connected to the radon source. The vacuum pump is connected to the radon chamber. A buffer chamber(160) is arranged in between the radon source and radon chamber. A gas flowing into the buffer chamber is absorbed by cooling in the buffer chamber and phase changed into the gas, thereby being supplied to the radon chamber.
    • 目的:提供一种用于测量氡气的标准装置,用于在通过缓冲室之后,将从氡气源提供的氡气供应至氡室,从而提高返回室的纯度,用于分配和吸收 氡室。 构成:用于测量氡的标准装置包括氡源(24),氡室(14)和真空泵(12)。 氡室连接到氡气源。 真空泵连接到氡室。 缓冲室(160)布置在氡气源和氡气室之间。 流入缓冲室的气体被缓冲室中的冷却吸收,相变成气体,从而供给到氡室。
    • 108. 发明公开
    • 삼중 동시 계수 분광계를 이용한 중성자 방사화 분석용 계측 장치 및 이를 이용한 핵종 선별 분석방법
    • 使用三重相关计数系统的核素分析和核素分析分析方法的仪器中子激活分析
    • KR1020120086078A
    • 2012-08-02
    • KR1020110007310
    • 2011-01-25
    • 한국원자력연구원
    • 선광민문종화정용삼김선하백성열
    • G01N23/222G01T7/00
    • G01N23/222G01N23/223G01N2223/0745G01N2223/106G01T1/167G01T7/02
    • PURPOSE: A neutron activation measuring device using a triple coincidence counting system and a nuclide selection analyzing method using the same are provided to perform a triple coincidence analysis on a real time basis after a measurement by connecting a measuring device and an analyzing device. CONSTITUTION: A neutron activation measuring device using a triple coincidence counting system comprises an automatic sample conveying device(600) and a nuclide measuring device(700). The automatic sample conveying device automatically inserts a sample(520) placed on a sample mount(510) into a body(530) and automatically transfers the sample to the sample mount after finishing a neutron activation measurement. The nuclide measuring device measures a radiation nuclide generated after radiating neutral particle beams or charged particles to the sample. The automatic sample conveying device comprises a gripping robot(610). The gripping robot grips the sample placed on the sample mount or places the sample on the body or grips or places the sample being inserted into the body on the sample mount by using pneumatic.
    • 目的:提供一种使用三重重合计数系统的中子激活测量装置和使用其的核素选择分析方法,通过连接测量装置和分析装置进行测量之后,实时地进行三重重合分析。 构成:使用三重重合计数系统的中子活化测量装置包括自动样品输送装置(600)和核素测量装置(700)。 自动样品输送装置将放置在样品支架(510)上的样品(520)自动插入体(530)中,并在完成中子活化测量之后自动将样品转移到样品座。 核素测量装置测量在向样品辐射中性粒子束或带电粒子之后产生的辐射核素。 自动样品输送装置包括夹持机器人(610)。 抓握机器人抓住放置在样品支架上的样品或将样品放置在身体上,或通过使用气动手柄或将样品插入到样品座上的样品。
    • 109. 发明公开
    • Background correction method for the minor isotopes of uranium in ultra-trace levels
    • 在超声波水平下的铀的微量同位素的背景校正方法
    • KR20120016441A
    • 2012-02-24
    • KR20100078805
    • 2010-08-16
    • KOREA ATOMIC ENERGY RES
    • PARK JONG HOCHOI IN HEESONG KYU SEOK
    • G01T1/167G01T7/00
    • G01T7/005G01T1/167
    • PURPOSE: A method of correcting the background of trace of uranium sub-isotope is provided to accurately measure a uranium isotope ratio by correcting the background of sub-isotope without a decrease in a signal or an increase in dark noise due to the use of conventional RPQ. CONSTITUTION: A method of correcting the background of trace of uranium sub-isotope is as follows. A detector is located on the mass between peaks of uranium isotope(S10). The amplitude of a signal corresponding to the mass between peaks depending on a change in the amplitude of a signal of uranium main-isotope 238U with a detector is measured(S20). Background for the uranium sub-isotope 234U is calculated with average of the signal corresponding to the mass between peaks(S30). A relation of uranium sub-isotope 234U with the background depending on the amplitude of the signal of uranium main-isotope 238U is made(S40).
    • 目的:提供一种纠正铀亚同位素痕迹背景的方法,以便通过校正亚同位素的背景来精确测量铀同位素比率,而不会由于使用常规的信号而导致信号的减少或暗噪声的增加 RPQ。 构成:修正铀亚同位素痕迹背景的方法如下。 检测器位于铀同位素峰之间的质量上(S10)。 测量与检测器的铀主同位素238U的信号的振幅的变化相对应的峰值之间的质量的信号的振幅(S20)。 使用对应于峰值之间的质量的信号的平均值计算铀亚同位素234U的背景(S30)。 铀亚同位素234U与背景的关系取决于铀主同位素238U信号的振幅(S40)。
    • 110. 发明授权
    • 원전 대형 폐 금속기기의 방사선량율을 이용한 비방사능 측정방법
    • 用于核电厂的弹性金属部件的剂量率的特定活性测量方法
    • KR101095624B1
    • 2011-12-19
    • KR1020110089797
    • 2011-09-05
    • (주)성우이앤티
    • 정성엽
    • G21C17/00G01T1/167
    • G21C17/10G01T1/167Y02E30/40
    • PURPOSE: A specific activity measuring method using a dose rate of a spent metal component for a nuclear power plant is provided to minimize a contamination measuring apparatus and measurement manpower by analyzing whole specific activity based on the partial measurement of an object. CONSTITUTION: In a specific activity measuring method using a dose rate of a spent metal component for a nuclear power plant, a number of a lattice group in the contamination site of an object is determined. A number or size of divided lattice is determined. A measurement device is arranged to measure radiation dose. A specific activity is measured by collecting a sample, and then specific activity is measured in a general lattice.
    • 目的:提供一种使用核动力装置的废金属部件的剂量率的比活度测量方法,以通过基于对象的部分测量分析整体特定活动来最小化污染测量装置和测量人力。 构成:在使用核动力装置的废金属成分的剂量率的比活性测定方法中,确定物体的污染部位的数量的格子组。 确定分割格数的数量或大小。 设置测量装置来测量辐射剂量。 通过收集样品来测量比活性,然后以普通晶格测量比活性。